Jeremy T. Busby - Concepedia

Author

Jeremy T. Busby

Also Known As

Busby, Jeremy, George Griffith, J. Busby, J. T. Busby, J. T. Busby *, J.T Busby, J.T. Busby, JT Busby, Jeremy Busby, Jeremy T Busby

146

Publications

6.5K

Citations

H-Index

Concepts

All Affiliations

Oak Ridge National Laboratory University of Michigan University of Wisconsin–Madison Idaho National Laboratory Pacific Northwest National Laboratory

About

Jeremy T. Busby is an author at Oak Ridge National Laboratory specializing in engineering, materials science, and microstructure.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	36	60	5.1K
2	Applied Physics	14	16	835
3	Health Sciences	1	1	148
4	Natural Sciences	1	1	79
5	Chemical Engineering	1	1	159

Jeremy T. Busby

Publications

Citations

H-Index

Page 1

	Year	Citations
Structural materials for fission & fusion energy S.J. Zinkle, Jeremy T. Busby Materials Today EngineeringRadiation Materials ScienceMechanical EngineeringUniform DensityFusion Materials	2009	1.2K
The relationship between hardness and yield stress in irradiated austenitic and ferritic steels Jeremy T. Busby, M.C. Hash, Gary S. Was Journal of Nuclear Materials Materials ScienceEngineeringHot WorkingYield StressHigh Strength Low Alloy Steel	2004	490
Materials challenges for nuclear systems Todd R. Allen, Jeremy T. Busby, M. K. Meyer, Materials Today	2010	425
Emulation of neutron irradiation effects with protons: validation of principle Gary S. Was, Jeremy T. Busby, Todd R. Allen, Journal of Nuclear Materials EngineeringNuclear PhysicsNeutron Irradiation EffectsNeutron SourceProton Therapy	2002	316
On the mechanism of radiation-induced segregation in austenitic Fe–Cr–Ni alloys Todd R. Allen, Jeremy T. Busby, Gary S. Was, Journal of Nuclear Materials Materials EngineeringMaterials ScienceEngineeringPhysicsRadiation-induced Segregation	1998	163
Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels Jeremy T. Busby, Gary S. Was, E. A. Kenik Journal of Nuclear Materials	2002	160
Zirconium alloys for supercritical water reactor applications: Challenges and possibilities Arthur T. Motta, Aylin Yilmazbayhan, Marcelo José Gomes da Silva, Journal of Nuclear Materials Materials ScienceMaterials EngineeringChemical EngineeringEngineeringCorrosion	2007	159
Microstructural evolution of proton irradiated T91 Gaurav Gupta, Zhijie Jiao, A.N. Ham, Journal of Nuclear Materials Microstructural EvolutionRadiation ChemistryPhysics	2006	151
Formulating the strength factor α for improved predictability of radiation hardening Lizhen Tan, Jeremy T. Busby Journal of Nuclear Materials Radiation HardeningEngineeringHealth SciencesRadiation Materials ScienceStrength Property	2015	148
Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation Todd R. Allen, Jian Gan, James I. Cole, Journal of Nuclear Materials Materials ScienceEngineeringChromium Oxide DispersionCorrosionMechanical Engineering	2007	139

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